ML17059A461
| ML17059A461 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point, 05000229  |
| Issue date: | 09/09/1994 |
| From: | Michael Case Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17059A462 | List: |
| References | |
| NUDOCS 9409220036 | |
| Download: ML17059A461 (16) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
149 License No.
DPR-63 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated January 6,
- 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.
DPR-63 is hereby amended to read as follows:
9409220036 9yocy09 PDR ADOCK 05000220 P
I
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B,
as revised through Amendment No. 149, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance to be implemented upon completion of the modification which physically removes the automatic reactor scram and main steam line isolation functions of the Hain Steam Line Radiation Monitor.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Michae J.
C se, Acting Director Project Directorate I-I Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Date of Issuance:
September 9,
1994
TTACHMEN TO LICENSE AMENDMENT DM 14 0
ACI ITY OPERATING LICENSE NO.
DPR-63 DOCKET O. 50-220 U
Revise Appendix A as follows:
emove Pa es 21 199 201 206 209 250 sert Pa es 21 199 201 206 209 250
BASES FOR 2.1.2 FUEL CLADDING-UMITINGSAFETY SYSTEM SETTING f-g.
The low pressure isolation of the main steam lines at 850 psig was provided to give protection against fast reactor depressurization and the resulting rapid cooldown of the vessel.
Advantage was taken of the scram feature which occurs when the main steam line isolation valves are closed, to provide for reactor shutdown so that high power operation at low reactor pressure does not occur, thus providing protection for the fuel cladding integrity safety limit. Operation of the reactor at pressures lower than 850 psig requires that the reactor mode switch be in the startup position where protection of the fuel cladding integrity safety limitis provided by the IRM high neutron flux scram.
Thus, the combination of main steam line isolation on reactor low pressure and isolation valve closure scram assures the availability of neutron flux scram protection over the entire range of applicability of the fuel cladding integrity safety limit. In addition, the isolation valve closure scram anticipates the pressure and flux transients which occur during normal or inadvertent isolation valve closure With the scrams set at <10% valve closure, there is no increase in neutron flux and peak pressure ifthe vessel dome is limited to 1141 psig (8, 9, 10)
The operator willset the pressure trip at greater than or equal to 850 psig and the isolation valve stem position scram setting at less than or equal to 10% of valve stem position from full open.
However, the actual pressure set point can be as much as 15.8 psi lower than the indicated 850 psig and the valve position set point can be as much as 2.5% of stem position greater.
These allowable deviations are due to instrument error, operator setting error and drift with time.
In addition to the above mentioned Limiting Safety System Setting, the scram dump volume high level scram trip (LCO 3.6.2) serves as a secondary backup to the Limiting Safety System Setting chosen.
This high level scram trip assures that scram capability willnot be impaired because of insufficient scram dump volume to accommodate the water discharged from the control rod drive hydraulic system as a result of a reactor scram (Section X-C.2.10) h.
The generator load rejection scram is provided to anticipate the rapid increase in pressure and neutron flux resulting from fast closure of the turbine control valves due to the worst case transient of a load rejection and subsequent failure of the bypass.
In fact, analysis (
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shows that heat flux does not increase from its initial value at all because of the fast action of the load rejection scram; thus, no significant change in MCPR occurs.
The turbine stop valve closure scram is provided for the same reasons as discussed in h above.
With a scram setting of s10% valve closure, the resultant transients are nearly the same as for those described in h above; and, thus, adequate margin exists.
0UFSAR AMENDMENTNO. Of, Ak, 149 21
TABLE3.6.2a (cont'd)
Nl IA Minimum No.
of Tripped or rI Minimum No. of Operable Instrument Channels per Operable SeiZaht Reactor Mode Switch Position in Which Function Must Be C
O CO CL
= M (6)
Main-Steam-Line Isolation Valve Position (7)
Deleted 4(h)(o)'
10 percent valve closure from full open (c)
(c) x
. (8)
Shutdown Position of Reactor Mode Switch (k) x (9)
Neutron Flux (a) IRM (i) Upscale 3(d)(o) a 96 percent of full scale (g)
(g)
(g)
AMENDMENTNO. Af, 149 199
TABLE4.6.2a N
EILrr)SK Instrument QhlnmLhat Instrument Channel
~li yfjiig (1)
Manual Scram (2)
. High Reactor Pressure (3)
High Drywall Pressure (4)
Low Reactor Water Level None None None Once/day Once per week Once per 3 months(1)
Once per 3 months(1)
Once per 3 months(
I None Once per 3 months(
I Once per 3 months(
I Once per 3 months("I (5)
High Water Level Scram Discharge Volume None Once per 3 months Once per 3 months (6)
Main-Steam-Line Isolation Valve Position None Once per 3 months Once per operating cycle (7)
Deleted AMENDMENTNO. 6$,,149 201
~I
TABLE3.6.2b (cont'd)
N MEN ATI HA NTIA E Minimum No.
of Tripped or Minimum No. of Operable Instrument.
Channels per Operable Reactor Mode Switch Position ln Which Function Must Be I
C O
'O ED V
ID IZ CL M
(4)
Deleted (5)
Low Reactor Pressure (6)
Low-Low-LowCondenser Vacuum 2(f) 2(f) a 850 psig a 7 in. mercury vacuum (a) x (7)
High Temperature Main Steam Line Tunnel 2(f) 200oF X
X AMENDMENTNO. Ak, 149 206
l
TABLE4.6.2b A
N E
A HA INITA Instrument GbanmdZmi Instrument Channel Qnlihruihn JKLhj:IQH (Main Steam, Cleanup and Shutdown)
(1)
Low-Low Reactor Water Level Once/day Once per 3 monthsl
)
Once per 3 monthsi
)
(2)
Manual Once during each major refueling outage MAIN-EAM-LIN
{3)
High Steam Flow Main-Steam Line Once/day Once per 3 monthsl I
Once per 3 monthsl I
(4)
Deleted (5)
Low Reactor Pressure Once/day Once per 3 monthsld)
Once per 3 monthsl I
AMENDMENTNO. Af, 149 209
I P